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SCALE Analyses of Scenarios in the TRISO-based Heat Pipe Microreactor Fuel Cycle

Technical Report ·
DOI:https://doi.org/10.2172/3002414· OSTI ID:3002414
This report documents the application of the SCALE code to the analysis of a TRistructural-ISOtropic (TRISO)-based heat pipe microreactor (HPMR) within the context of its nuclear fuel cycle stages. The evaluation was conducted in support of the US Nuclear Regulatory Commission’s ongoing efforts to assess modeling capabilities for advanced non–light-water reactor technologies. The generic HPMR selected as a representative microreactor concept features a compact core design that incorporates TRISO fuel compacts, passive heat removal via heat pipes, and a transportable configuration intended for deployment in remote environments.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE; USNRC
DOE Contract Number:
AC05-00OR22725
OSTI ID:
3002414
Report Number(s):
ORNL-TM--2025-3914
Country of Publication:
United States
Language:
English

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